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| | author name = Condra D | | | author name = Condra D |
| | author affiliation = Oak Ridge Institute for Science & Education | | | author affiliation = Oak Ridge Institute for Science & Education |
| | addressee name = Kottan J J | | | addressee name = Kottan J |
| | addressee affiliation = NRC/RGN-I | | | addressee affiliation = NRC/RGN-I |
| | docket = 05000247 | | | docket = 05000247 |
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| =Text= | | =Text= |
| {{#Wiki_filter:4B ORISE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S. Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406 | | {{#Wiki_filter:4B O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S.Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW | | REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW I YORK |
| [INSPECTION REPORT NO. 050-247/2007-0031 | | [INSPECTION REPORT NO. 050-247/2007-0031 [RFTA NO. 07-0011 |
| [RFTA NO. 07-0011 I YORK >ear Mr. Icottan: The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from ths licrnsee and modified based on a phone :onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1. | | >ear Mr. Icottan: |
| >amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total .adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. | | The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from t h s licrnsee and modified based on a phone |
| The pertinent procedure references are provided in each specific table. | | :onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1. |
| 3RISE's Quality Control (QC) requirements were met for these analyses. | | >amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total |
| The QC fdes are available for Tour review upon requrst. Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. | | .adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. The pertinent procedure references are provided in each specific table. |
| Sincerely, Dale Condra, Manager '>aboratory RDC:LYTI.at Znclosures T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN S. Roberts, ORISE File 1697 SA23 J. E \Y.htc, NRC Regiot . Abelquist, ORISE zp 75 I W s lg VI Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra | | 3RISE's Quality Control (QC) requirements were met for these analyses. The QC fdes are available for Tour review upon requrst. |
| @orau.org TABLE 1 - ORISE NRC Region I Collection Collection Date Sample ID Sample ID Time 1 697WO 142 Mw-54-38'- | | Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. |
| (00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24 TABLE 2 ORISE Sample ID 1697YV0142 1697M0143 1697YV0144 1697YV0145 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCWAN, NEW YORK Radionuclide Concentrations, TPUs, and MDCs" @Ci/L)
| | Sincerely, Dale Condra, Manager zp |
| CO-58 CO-60 cs-l34 cs-w7 NRC Region I Sample ID m-54-38'-(001)
| | '>aboratory 75 I |
| O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 m-54-59'-(001)
| | RDC:LYTI.at W Znclosures s T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN SA23 J. \Y.htc, NRC Regiot E . Abelquist, ORISE lg VI S.Roberts, ORISE File 1697 Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org |
| -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 m-54-125'-(001)
| |
| -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 m-54-146'-(001)
| |
| -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8 1) 1697W0146 I m-54-174'-(001)
| |
| I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I(
| |
| TABLE 3 ORISE Sample ID ~ Radionuclide Concentrations, TPUs, and MDCs" @Ci/L)
| |
| NRC Region I Sample ID Fe-55h Ni-63' H-3* 1697W0142 MW-54-38'-(001)
| |
| -13 k lge , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 InlanPmr Power Statlon 169W0144 1697W0145 1697W0146 1697W0147 - Fra~ectr/l697/DaraTables/2007-07-31 Intern Data Tables 1697 Set 24 I, I Mw-54-125'-(001)
| |
| -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290 MW-54-146'-(001)
| |
| -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 MW-54-174'-(001)
| |
| -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 Mw-54-192'-(001)
| |
| -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 TABLE 4 ORISE Sample ID CONCENTRATIONS OF TECHNETIUM-99 , IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide NRC Region I Concentrations, Sample ID TPUs, and MDCs" @Q/L) b 1697W0142 I MW-54-38'-(001)
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| I 3.1 ? 7.6 , 13.0 (1 1697W0143 1 MW-54-59'-(001)
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| I -1.2 ? 7.5 , 13.0 11 1697W0144 1 MW-54-125'-(001)
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| I 3.5 i 7.7 , 13.0 1) 1697W0145 1 MW-54-146'-(001)
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| I -0.3 k 7.5 . 13.0 I1 .. I1 1697W0146 i Mw-54-174'-(001) 1 4.5 k 7.7 . 13.0 11 1697W0147 I MW-54-192'-1001)
| |
| I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 Intern Data Tables 1697 Set 24 TABLE 5 ORISE Sample ID 1697W0142 1697W0143 1697W0144
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| 1697W0145 1697W0146 1697W0147 Radionuclide Concentrations, TPUs, and MDCS" @Ci/L) NRC Region I Sample ID Mw-54-38'-(001) 12.2 rt l.lb , 0.9 m-54-59'-(001) 3.09 i 0.67 , 0.84 m-54-125'-(001) 21.3 i 1.5 , 0.8 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 Mw-54-192'-(001) 22.5 | | TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Date Collection Sample ID Sample ID Time 1697WO142 Mw-54-38'-(00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24 |
| * 16 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31 Inte- Data Tables 1697 Set 24 TABLE 6 ORISE NRC Region I Sample ID Sample ID 1697W0142 Mw-54-38'-(001) 1697W0143 MW-54-59'-(001) 1697W0144 MW-54-125'-(001) 1697W0145 MW-54-146'-(001) 1697W0146 MW-54-174'-(001) 1697W0147 MW-54-192'-(001)
| | |
| Radionuclide Concentrations' (pCi/L for water) Am-241 Cm-242 Cm-243/244 Np-237 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t B TABLE 6 (Continued) | | TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION B U C W A N , NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCs" @Ci/L) |
| CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i TABLE 7 ORISE NRC Region I CONCENTRATIONS OF PLUTONIUM-241 IN DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, Sample ID 1697W0142 1697W0143 SampleID TPUs, and MDCs" @Ci/L) | | Sample ID Sample ID CO-58 CO-60 cs-l34 cs-w7 1697YV0142 m-54-38'-(001) O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 1697M0143 m-54-59'-(001) -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 1697YV0144 m-54-125'-(001) -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 1697YV0145 m-54-146'-(001) -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8 |
| Mw-54-38'-(001) | | : 1) 1697W0146 I m-54-174'-(001) I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I( |
| -2 | | |
| * 37b 63 Mw-54-59'-(001) 8 | | TABLE 3 |
| * 34 59 Mw-54-125'-(001) 9 i 35 The MDCS are afrer the comma. bUn~ercmoes represmr he 9594 confidence lwd, bascd on total propagated uncertainties 1697W0145 Mw-54-146'-(001) | | ~ |
| Indian Point Power Station 5
| | Radionuclide Concentrations, ORISE N R C Region I TPUs, and MDCs" @Ci/L) |
| * 34 59 Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24 1697W0146 Mw-54-174'-(001) 3 | | Sample ID Sample ID Fe-55h Ni-63' H-3* |
| * 37 63 1697W0147 Mw-54-192'-(001) | | 1697W0142 MW-54-38'-(001) -13 k l g e , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 I , |
| -6 t 36 62 TABLE 8 ORISE NRC Region I Sample ID Sample ID Radionuclide Concentrations, TPUs, and MDCs' @Ci/L) 1697W0142 1697W0143 1697W0144 1697W0145 1697W0146 1697W0147 me mcs are after the coma. bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes. | | I 169W0144 Mw-54-125'-(001) -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290 |
| MW-54-38'-(001) | | - 1697W0145 MW-54-146'-(001) -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 1697W0146 MW-54-174'-(001) -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 1697W0147 Mw-54-192'-(001) -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 InlanPmr Power Statlon I n t e r n Data Tables 1697 Set 24 Fra~ectr/l697/DaraTables/2007-07-31 |
| -0.8 f 9.4b , 16.1 MW-54-59'-(001) | | |
| -7.2 k 9.4 , 16.1 MW-54-125'-(001) | | TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 |
| -6.0 f 9.4 , 16.1 MW-54-146'-(001) 0.3 f 9.5 , 16.1 MW-54-174'-(001) | | , I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCs" |
| -1.7 f 9.4 , 16.1 ME-54-1 92'-(001) | | @Q/L) 1697W0142 I MW-54-38'-(001) I 3.1 ? 7.6b , 13.0 (1 1697W0143 1 MW-54-59'-(001) I -1.2 ? 7.5 , 13.0 1 1 I 11I) 1697W0144 1697W0145 1697W0146 1 |
| -5.3 i 9.4 , 16.1 - In&m Pomr Power stauon Pr~ects/lG9l/Data Tabler/2007-07-31 InteMl DataTables 1697 Set 24}} | | i MW-54-125'-(001) |
| | MW-54-146'-(001) |
| | Mw-54-174'-(001) |
| | I 1 |
| | 3.5 |
| | -0.3 4.5 i 7.7 k 7.5 k 7.7 |
| | , 13.0 13.0 13.0 1I 11 1697W0147 I MW-54-192'-1001) I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 I n t e r n Data Tables 1697 Set 24 |
| | |
| | TABLE 5 Radionuclide ORISE NRC Region I Concentrations, TPUs, and Sample ID Sample ID MDCS" @Ci/L) 1697W0142 Mw-54-38'-(001) 12.2 rt l.lb , 0.9 1697W0143 m-54-59'-(001) 3.09 i 0.67 , 0.84 1697W0144 m-54-125'-(001) 21.3 i 1.5 , 0.8 1697W0145 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 1697W0146 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 1697W0147 Mw-54-192'-(001) 22.5 |
| | * 1 6 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31Inte- Data Tables 1697 Set 24 |
| | |
| | TABLE 6 ORISE NRC Region I Radionuclide Concentrations' (pCi/L for water) |
| | Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0142 Mw-54-38'-(001) 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 1697W0143 MW-54-59'-(001) 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 1697W0144 MW-54-125'-(001) 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 1697W0145 MW-54-146'-(001) 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 1697W0146 MW-54-174'-(001) 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 1697W0147 MW-54-192'-(001) -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t |
| | B |
| | |
| | TABLE 6 (Continued) |
| | CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i |
| | |
| | TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID SampleID TPUs, and MDCs" @Ci/L) 1697W0142 Mw-54-38'-(001) -2 |
| | * 37b 63 1697W0143 Mw-54-59'-(001) 8 |
| | * 34 59 Mw-54-125'-(001) 9 i 35 1697W0145 Mw-54-146'-(001) 5 |
| | * 34 59 1697W0146 Mw-54-174'-(001) 3 |
| | * 37 63 1697W0147 Mw-54-192'-(001) -6 t 36 62 T h e MDCS are afrer the comma. |
| | bUn~ercmoesrepresmr h e 9594 confidence lwd, bascd on total propagated uncertainties Indian Point Power Station Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24 |
| | |
| | TABLE 8 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs' @Ci/L) 1697W0142 MW-54-38'-(001) -0.8 f 9.4b , 16.1 1697W0143 MW-54-59'-(001) -7.2 k 9.4 , 16.1 - |
| | 1697W0144 MW-54-125'-(001) -6.0 f 9.4 , 16.1 1697W0145 MW-54-146'-(001) 0.3 f 9.5 , 16.1 1697W0146 MW-54-174'-(001) -1.7 f 9.4 , 16.1 1697W0147 ME-54-192'-(001) -5.3 i 9.4 , 16.1 m e m c s are after the c o m a . |
| | bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes. |
| | In&m Pomr Power stauon Pr~ects/lG9l/DataTabler/2007-07-31 InteMl DataTables 1697 Set 24}} |
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ML0729502532007-10-10010 October 2007
Siren Schedule 11 X 17 Dtd 10/10/07
ML0728403122007-07-31031 July 2007
Report for Analysis for Samples from Set Twenty-Four from the Indian Point Power Station, Buchanan, New York. Dtd. July 31, 2007
ML0728402552007-05-0303 May 2007
Interim Report for Completed Analysis for Samples from Set Twenty-One from the Indian Point Power Station, Buchanan, New York. Dtd. May 3, 2007
ML0713102862007-03-20020 March 2007
E-Mail from D. Winslow of GZA to M. Barvenik of GZA, J. Noggle of USNRC and J. Adler of Entergy, Regarding GZA Results
ML0713100562007-02-15015 February 2007
E-Mail from T. Rice of NYSDEC to Various, Regarding Latest State Results
ML0713100452007-02-12012 February 2007
E-Mail from P. Donahue of Entergy to T. Rice of NYSDEC, Regarding Split Sample Data
ML0713005932007-01-24024 January 2007
E-Mail from D. Gray of Entergy to J. Noggle of USNRC, Regarding Historical Sr Data
ML0709405042007-01-12012 January 2007
Ltr from Orise Dtd 01/12/2007, Final Letter Report for Requested Analyses of Six Water Samples, Set Eleven, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006-007) (Rfta No. 06-001)
IR 05000247/20060072007-01-0404 January 2007
Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001)
ML0709406182007-01-0404 January 2007
Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001)
ML0701105612006-12-15015 December 2006
Interim Report for Completed Analyses for Samples from Sets Fifteen and Sixteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001)
ML0704003112006-12-0404 December 2006
E-Mail from T. Rice of Department of Environmental Conservation to J. Adler of Entergy, and J. Noggle and J. White of USNRC, Regarding Latest State Data
ML0704002992006-11-28028 November 2006
E-Mail from T. Rice of Department of Environmental Conservation to Various, Regarding Latest State Results
ML0701105482006-11-17017 November 2006
Interim Report for Requested Analyses for Samples from Sets Eleven Through Fourteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001)
ML0628302122006-06-15015 June 2006
E-mail from R. Lavera of Entergy to J. Noggle of NRC, Regarding Sample Log
ML0618605182006-04-26026 April 2006
E-mail from R. Sachatello of Entergy to M. Barvenik and D. Sinslow of GZA, Regarding Pressure Test Discussion with GZA
ML0620001512006-04-13013 April 2006
E-mail from K. Mcmullian, Entergy, to J. Boska, NRR, Et Al., IPEC Status Report April 13
ML0610006912006-03-27027 March 2006
Units 1 & 2 Tritium History (GL-80-10), in Nci/Ml
2024-06-04
[Table view]
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000003/20240022024-08-0606 August 2024
NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24171A0122024-06-18018 June 2024
Reply to a Notice of Violation EA-24-037
ML24156A1162024-06-0404 June 2024
Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
IR 05000003/20240052024-05-21021 May 2024
and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation
ML24128A0632024-05-0707 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024
HDI Annual Occupational Radiation Exposure Data Reports - 2023
ML24116A2412024-04-25025 April 2024
Annual Environmental Protection Plan Report
ML24114A2282024-04-23023 April 2024
Annual Radioactive Effluent Release Report
L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)
ML24080A1722024-03-20020 March 2024
Reply to a Notice of Violation EA-2024-010
IR 05000003/20240012024-03-20020 March 2024
NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only)
ML24045A0882024-02-22022 February 2024
Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments
ML24053A0642024-02-22022 February 2024
2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
IR 05000003/20230042024-02-22022 February 2024
NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation
ML24011A1982024-01-12012 January 2024
ISFSI, Notice of Organization Change for Site Vice President
ML23342A1082024-01-0909 January 2024
– Independent Spent Fuel Storage Installation Security Inspection Plan
ML23353A1742023-12-19019 December 2023
ISFSI, Emergency Plan, Revision 23-04
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
ML23326A1322023-12-0505 December 2023
Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan
ML23339A0442023-12-0505 December 2023
Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan
ML23338A2262023-12-0404 December 2023
Signed Amendment No. 27 to Indemnity Agreement No. B-19
ML23356A0212023-12-0101 December 2023
American Nuclear Insurers, Secondary Financial Protection (SFP) Program
ML23242A2772023-11-30030 November 2023
NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs
ML23338A0482023-11-30030 November 2023
ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28
ML22339A1572023-11-27027 November 2023
Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E
IR 05000003/20230032023-11-21021 November 2023
NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003
ML23100A1252023-11-17017 November 2023
Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement
ML23100A1172023-11-17017 November 2023
NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition
ML23050A0032023-11-17017 November 2023
Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage
ML23100A1432023-11-16016 November 2023
Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286)
L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023
Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point
ML23064A0002023-11-13013 November 2023
NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments
ML23306A0992023-11-0202 November 2023
and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7)
ML23063A1432023-11-0101 November 2023
Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50
ML23292A0262023-10-19019 October 2023
LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI
ML23289A1582023-10-16016 October 2023
Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit
ML23270A0082023-09-27027 September 2023
Registration of Spent Fuel Casks
ML23237A5712023-09-22022 September 2023
09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
ML23242A2182023-09-12012 September 2023
IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286)
ML23250A0812023-09-0707 September 2023
Registration of Spent Fuel Casks
ML23255A0142023-08-31031 August 2023
LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report
IR 05000003/20230022023-08-22022 August 2023
NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002
ML23227A1852023-08-15015 August 2023
Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme
ML23222A1442023-08-10010 August 2023
Registration of Spent Fuel Casks
ML23208A1642023-07-26026 July 2023
Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater
ML23200A0422023-07-19019 July 2023
Registration of Spent Fuel Casks
ML23235A0602023-07-17017 July 2023
LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
2024-09-18
[Table view]
Category:Report
MONTHYEARML22013A7062022-01-13013 January 2022
Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G
ML21056A0782021-04-0707 April 2021
Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51)
NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021
Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement
ML20259A2172020-09-14014 September 2020
Commitment Change Summary Report
ML20260H0722020-06-18018 June 2020
IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec
ML20122A1052020-05-27027 May 2020
Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl
ML20100F6352020-04-0808 April 2020
Expert Team Final Report
NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019
Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML19252A3182019-09-0909 September 2019
Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019
NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019
Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
ML19114A0742019-04-22022 April 2019
Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019
NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019
Request for Approval of a Certified Fuel Handler Training and Retraining Program
ML18098A0882018-04-0606 April 2018
Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability
NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018
Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability
NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017
Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center
ML17349A1562017-12-0808 December 2017
Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes
ML17279A2472017-10-0606 October 2017
2017 Annual Assessment Meeting Written Comments Compilation
ML17222A2392017-10-0404 October 2017
NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations
ML17289A6552017-10-0202 October 2017
Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9
NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017
Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017
ML17096A2122017-03-23023 March 2017
Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017)
NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017
License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan
ML17096A2112017-01-0404 January 2017
Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017)
ML16280A2282016-09-19019 September 2016
Indian Point 2 Technical Requirements Manual
NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016
Indian Point 2 Technical Requirements Manual
NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016
HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.
ML16250A2762016-09-13013 September 2016
Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal
NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016
Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3
ML18115A0592016-06-28028 June 2016
After Action Report/Improvement Plan, Drill Date June 28, 2016
ML17052A2662015-10-0202 October 2015
Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee
NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015
Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update
NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015
Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3
NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015
Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015
2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015
Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project
NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015
Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015
ML15062A2002015-02-19019 February 2015
NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary)
NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015
Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval
ML15061A2772014-12-31031 December 2014
WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation.
NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014
Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...
ML14329A1952014-11-0404 November 2014
NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels
NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014
10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014
ML14304A7012014-09-16016 September 2014
Reliability Needs Assessment
ML15166A0702014-08-31031 August 2014
Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014
NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014
Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014
Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5
NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014
Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5
ML14168A0592014-06-0505 June 2014
Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5
ML14168A0602014-06-0505 June 2014
Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5
ML14168A0612014-06-0505 June 2014
Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5
2022-01-13
[Table view]
Category:Miscellaneous
MONTHYEARML22013A7062022-01-13013 January 2022
Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G
ML20260H0722020-06-18018 June 2020
IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec
ML20122A1052020-05-27027 May 2020
Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl
NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019
Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML19252A3182019-09-0909 September 2019
Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019
NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019
Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
ML19114A0742019-04-22022 April 2019
Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019
NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019
Request for Approval of a Certified Fuel Handler Training and Retraining Program
ML17279A2472017-10-0606 October 2017
2017 Annual Assessment Meeting Written Comments Compilation
ML17222A2392017-10-0404 October 2017
NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations
NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017
License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan
NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016
Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3
NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015
Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update
NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015
Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3
NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015
Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015
2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015
Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project
NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015
Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval
NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014
Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...
ML14329A1952014-11-0404 November 2014
NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels
NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014
10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014
ML15166A0702014-08-31031 August 2014
Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014
NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014
Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML14141A5402014-05-0909 May 2014
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Text
4B O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S.Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW I YORK
[INSPECTION REPORT NO. 050-247/2007-0031 [RFTA NO. 07-0011
>ear Mr. Icottan:
The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from t h s licrnsee and modified based on a phone
- onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1.
>amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total
.adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. The pertinent procedure references are provided in each specific table.
3RISE's Quality Control (QC) requirements were met for these analyses. The QC fdes are available for Tour review upon requrst.
Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager zp
'>aboratory 75 I
RDC:LYTI.at W Znclosures s T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN SA23 J. \Y.htc, NRC Regiot E . Abelquist, ORISE lg VI S.Roberts, ORISE File 1697 Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Date Collection Sample ID Sample ID Time 1697WO142 Mw-54-38'-(00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION B U C W A N , NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCs" @Ci/L)
Sample ID Sample ID CO-58 CO-60 cs-l34 cs-w7 1697YV0142 m-54-38'-(001) O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 1697M0143 m-54-59'-(001) -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 1697YV0144 m-54-125'-(001) -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 1697YV0145 m-54-146'-(001) -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8
- 1) 1697W0146 I m-54-174'-(001) I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I(
TABLE 3
~
Radionuclide Concentrations, ORISE N R C Region I TPUs, and MDCs" @Ci/L)
Sample ID Sample ID Fe-55h Ni-63' H-3*
1697W0142 MW-54-38'-(001) -13 k l g e , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 I ,
I 169W0144 Mw-54-125'-(001) -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290
- 1697W0145 MW-54-146'-(001) -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 1697W0146 MW-54-174'-(001) -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 1697W0147 Mw-54-192'-(001) -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 InlanPmr Power Statlon I n t e r n Data Tables 1697 Set 24 Fra~ectr/l697/DaraTables/2007-07-31
TABLE 4 CONCENTRATIONS OF TECHNETIUM-99
, I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCs"
@Q/L) 1697W0142 I MW-54-38'-(001) I 3.1 ? 7.6b , 13.0 (1 1697W0143 1 MW-54-59'-(001) I -1.2 ? 7.5 , 13.0 1 1 I 11I) 1697W0144 1697W0145 1697W0146 1
i MW-54-125'-(001)
MW-54-146'-(001)
Mw-54-174'-(001)
I 1
3.5
-0.3 4.5 i 7.7 k 7.5 k 7.7
, 13.0 13.0 13.0 1I 11 1697W0147 I MW-54-192'-1001) I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 I n t e r n Data Tables 1697 Set 24
TABLE 5 Radionuclide ORISE NRC Region I Concentrations, TPUs, and Sample ID Sample ID MDCS" @Ci/L) 1697W0142 Mw-54-38'-(001) 12.2 rt l.lb , 0.9 1697W0143 m-54-59'-(001) 3.09 i 0.67 , 0.84 1697W0144 m-54-125'-(001) 21.3 i 1.5 , 0.8 1697W0145 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 1697W0146 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 1697W0147 Mw-54-192'-(001) 22.5
- 1 6 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31Inte- Data Tables 1697 Set 24
TABLE 6 ORISE NRC Region I Radionuclide Concentrations' (pCi/L for water)
Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0142 Mw-54-38'-(001) 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 1697W0143 MW-54-59'-(001) 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 1697W0144 MW-54-125'-(001) 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 1697W0145 MW-54-146'-(001) 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 1697W0146 MW-54-174'-(001) 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 1697W0147 MW-54-192'-(001) -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t
B
TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID SampleID TPUs, and MDCs" @Ci/L) 1697W0142 Mw-54-38'-(001) -2
- 37b 63 1697W0143 Mw-54-59'-(001) 8
- 34 59 Mw-54-125'-(001) 9 i 35 1697W0145 Mw-54-146'-(001) 5
- 34 59 1697W0146 Mw-54-174'-(001) 3
- 37 63 1697W0147 Mw-54-192'-(001) -6 t 36 62 T h e MDCS are afrer the comma.
bUn~ercmoesrepresmr h e 9594 confidence lwd, bascd on total propagated uncertainties Indian Point Power Station Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24
TABLE 8 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs' @Ci/L) 1697W0142 MW-54-38'-(001) -0.8 f 9.4b , 16.1 1697W0143 MW-54-59'-(001) -7.2 k 9.4 , 16.1 -
1697W0144 MW-54-125'-(001) -6.0 f 9.4 , 16.1 1697W0145 MW-54-146'-(001) 0.3 f 9.5 , 16.1 1697W0146 MW-54-174'-(001) -1.7 f 9.4 , 16.1 1697W0147 ME-54-192'-(001) -5.3 i 9.4 , 16.1 m e m c s are after the c o m a .
bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes.
In&m Pomr Power stauon Pr~ects/lG9l/DataTabler/2007-07-31 InteMl DataTables 1697 Set 24
